FUKUYA Koji | Institute of Nuclear Safety System, Inc.
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概要
関連著者
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FUKUYA Koji
Institute of Nuclear Safety System, Inc.
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Fukuya Koji
Institute Of Nuclear Safety System
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FUJII Katsuhiko
Institute of Nuclear Safety System
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Fukuya K
Inst. Of Nuclear Safety System
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Fukuya K
Institute Of Nuclear Safety System
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Fukuya Kohji
Institute Of Nuclear Safety System
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Fujii K
Institute Of Nuclear Safety System
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TORIMARU Tadahiko
Nippon Nuclear Fuel Development
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NISHIOKA Hiromasa
Institute of Nuclear Safety System
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KITSUNAI Yuji
Nippon Nuclear Fuel Development
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NAKANO Morihito
Institute of Nuclear Safety System
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Nakano Morihito
Institute Of Nuclear Safety System Inc.
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笠田 竜太
京都大学エネルギー理工学研究所
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TERACHI Takumi
Institute of Nuclear Safety System, Inc.
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YAMADA Takuyo
Institute of Nuclear Safety System, Inc.
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MIYAMOTO Tomoki
Institute of Nuclear Safety System, Inc.
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ARIOKA Koji
Institute of Nuclear Safety System, Inc.
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木村 晃彦
京都大学エネルギー理工学研究所
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KAMAYA Masayuki
Institute of Nuclear Safety System, Inc.
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KITAMURA Takayuki
Kyoto University
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Kasada Ryuta
Institute of Advanced Energy, Kyoto University
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Kimura Akihiko
Institute of Advanced Energy, Kyoto University
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KIMURA Itsuro
Institute of Nuclear Technology, Institute of Nuclear Safety Systems, Inc.
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福谷 耕司
株式会社原子力安全システム研究所技術システム研究所
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Fukuya Koji
Institute Of Nuclear Safety System Inc.
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Fukuya Koji
Institute Of Nuclear Technology Institute Of Nuclear Safety System Incorporated
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Kitamura Takayuki
Kyoto Univ. Kyoto Jpn
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Kimura Itsuro
Institute Of Nuclear Safety System
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Arioka Koji
Institute Of Nuclear Safety System Inc.
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Kasada Ryuta
Institute Of Advanced Energy Kyoto University
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Yamada Takuyo
Institute Of Nuclear Safety System Inc.
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Terachi Takumi
Institute Of Nuclear Safety System Inc.
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NAKATA Hayato
Institute of Nuclear Technology, Institute of Nuclear Safety System Incorporated
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Kimura Akihiko
Institute Of Advanced Energy Kyoto University
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中田 早人
近畿大 原子力研
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Kamaya Masayuki
Institute Of Nuclear Safety System Inc.
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Kamaya Masayuki
Institute For Nuclear Safety System Inc.
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Miyamoto Tomoki
Institute Of Nuclear Safety System Inc.
著作論文
- Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water : Effect of Chromium Content in Alloys and Dissolved Hydrogen
- Angular Distribution of Slip Steps by Three-Dimensional Polycrystalline Model for Stainless Steel
- Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation
- IASCC Initiation in Highly Irradiated Stainless Steels under Uniaxial Constant Load Conditions
- Effects of Dissolved Hydrogen and Strain Rate on IASCC Behavior in Highly Irradiated Stainless Steels
- Deformation Structure in Highly Irradiated Stainless Steels
- Separation of Microstructural and Microchemical Effects in Irradiation Assisted Stress Corrosion Cracking using Post-irradiation Annealing
- IASCC Susceptibility and Slow Tensile Properties of Highly-irradiated 316 Stainless Steels
- Role of Radiation-Induced Grain Boundary Segregation in Irradiation Assisted Stress Corrosion Cracking
- A Multicomponent Model of Radiation-induced Segregation for Commercial Stainless Steels
- Grain Boundary Phosphorus Segregation in Thermally Aged Low Alloy Steels
- Calculation of Gamma Induced Displacement Cross-sections of Iron Considering Positron Contribution and Using Standard Damage Model